U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/19/95 - 12/20/95 ** EVENT NUMBERS ** 29738 29739 29740 29741 29742 29743 29744 29745 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29738 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: POWER RESOURCES INC. |NOTIFICATION DATE: 12/19/95 | | CITY: DOUGLAS REGION: 4 |NOTIFICATION TIME: 11:58 [ET]| | COUNTY: CONVERSE STATE: WY |EVENT DATE: 12/14/95 | |LICENSE#: SUA1511 AGREEMENT: N |EVENT TIME: 00:00[MST]| | DOCKET: |LAST UPDATE DATE: 12/19/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |YANDELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: KEARNEY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REPORTED THAT A MONITORING WELL HAS BEEN PLACED ON EXCURSION | | STATUS. | | | | THE LICENSEE REPORTED THAT MONITORING WELL M8A FOR AN IN-SITU URANIUM MINE | | HAS BEEN PLACED IN "EXCURSION STATUS" DUE TO HIGH CHLORIDE AND CONDUCTIVITY | | MEASUREMENTS. ON 12/14/95, THE WELL WAS SAMPLED WITH THE FOLLOWING | | RESULTS: CHLORIDES 39 mg/l | | BICARBONATE 250 mg/l | | CONDUCTIVITY 723 æmho/cm | | | | ON 12/18/95, THE WELL WAS SAMPLED AGAIN WITH THE FOLLOWING RESULTS: | | CHLORIDES 36 mg/l | | BICARBONATE 264 mg/l | | CONDUCTIVITY 747 æmho/cm | | | | THE MONITORING LIMITS ARE: CHLORIDES 9 mg/l | | BICARBONATE 287 mg/l | | CONDUCTIVITY 688 æmho/cm | | | | THE LICENSEE IS REQUIRED TO CONTACT THE NRC OPERATIONS CENTER WITHIN 24 | | HOURS OF PLACING A WELL IN EXCURSION STATUS. THE LICENSEE PLANS TO CONTACT | | REGION IV DIRECTLY REGARDING THIS MATTER. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29739 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 12:13 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 10:47[CST]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |YANDELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |D'AMICO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 85 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO UNIDENTIFIED DRYWELL LEAKAGE GREATER THAN | | FIVE GPM. | | | | AT 1047, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO DRYWELL UNIDENTIFIED | | LEAKAGE OF GREATER THAN FIVE GPM. THE LICENSEE HAD BEEN MONITORING AN | | INCREASING TREND IN DRYWELL UNIDENTIFIED LEAKAGE BEFORE THE EVENT. (THE | | UNIDENTIFIED LEAKAGE HAD BEEN CALCULATED TO BE APPROXIMATELY 2.5 GPM). | | | | THIS MORNING, THE 'B' REACTOR RECIRCULATION PUMP TRIPPED WITHOUT PRIOR | | WARNING, THEN FAILED TO RESTART IN SLOW SPEED. ADDITIONALLY, THE 'A' PUMP | | SHIFTED TO SLOW SPEED. AT 0841, OPERATORS MANUALLY SCRAMMED THE PLANT TO | | PREVENT ENTRY INTO THE POTENTIAL INSTABILITY REGION OF THE POWER/FLOW MAP. | | THE SCRAM WAS UNCOMPLICATED, WITH ALL RODS INSERTING PROPERLY. FOLLOWING | | THE SCRAM, REACTOR WATER LEVEL DECREASED TO THE LEVEL 3 SETPOINT (DUE TO | | NORMAL SHRINK), AND THE LICENSEE ENTERED THE EMERGENCY PROCEDURES. | | FEEDWATER FLOW WAS INCREASED, AND THE FEEDWATER PUMPS SUBSEQUENTLY TRIPPED | | AT THE REACTOR VESSEL HIGH LEVEL (LEVEL 8) SETPOINT. DUE TO THE INJECTION | | OF COLD WATER, REACTOR PRESSURE DECREASED RAPIDLY, AND OPERATORS CLOSED THE | | MAIN STEAM ISOLATION VALVES TO RECOVER PRESSURE AND CONTROL THE COOLDOWN | | RATE. | | | | APPROXIMATELY ONE HOUR AFTER THE SCRAM, THE LICENSEE NOTICED AN INCREASE IN | | UNIDENTIFIED LEAKAGE TO APPROXIMATELY 5.0 GPM. UNIDENTIFIED LEAKAGE | | INCREASED TO A MAXIMUM OF 5.6 GPM, BEFORE DECREASING TO THE PRESENT LEVEL | | OF 4.6 GPM. THE LICENSEE CONTINUES TO MONITOR THE LEAKAGE, AND IS PREPARING | | TO MAKE A DRYWELL ENTRY TO IDENTIFY THE SOURCE. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. | | | | * * * UPDATE 1341 12/19/95 FROM TURNER TAKEN BY STRANSKY * * * | | | | THE DRYWELL ENTRY IS STILL ONGOING; HOWEVER, THE LICENSEE REPORTED THAT THE | | HPCS INJECTION CHECK VALVE APPEARS TO BE THE SOURCE OF THE EXCESSIVE | | LEAKAGE. THE LICENSEE CONTINUES TO MONITOR UNIDENTIFIED LEAKAGE AND IS | | LOOKING FOR OTHER SOURCES OF LEAKAGE IN THE DRYWELL. THE PLANT REMAINS IN | | THE UNUSUAL EVENT WHILE THESE ACTIVITIES CONTINUE. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO(YANDELL). | | | | * * * UPDATE 1633 12/19/95 FROM TURNER TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1526 CST. LEAKAGE FROM THE HPCS | | INJECTION CHECK VALVE WAS STOPPED BY CLOSING A MANUAL ISOLATION VALVE. THE | | LICENSEE PLANS TO REPAIR THE CHECK VALVE. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED. NOTIFIED R4DO(YANDELL), EO(HOLAHAN), FEMA(AUSTIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29740 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: CLARKSON |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHYMLOCK RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VALVE MAY HAVE BEEN UNABLE TO CLOSE AGAINST DIFFERENTIAL PRESSURE DUE TO | | INCORRECT GEAR RATIO IN MOTOR OPERATOR. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON NOVEMBER 29, 1995, WITH THE UNIT 1 REACTOR SHUT DOWN, DURING VOTES | | TESTING, 1RC-6 WAS FOUND TO HAVE A DIFFERENT STROKE TIME THAN WAS EXPECTED. | | THE ACTUAL STROKE TIME OBSERVED WAS 7.5 SECONDS WHILE THE EXPECTED STROKE | | TIME WAS 19.9 SECONDS. 1RC-6 IS THE CONTAINMENT ISOLATION VALVE FOR THE | | PRESSURIZER WATER SPACE SAMPLE. SUBSEQUENT ANALYSIS USING STROKE LENGTH AND | | STROKE TIME REVEALED THAT THE ACTUAL GEAR RATIO OF THIS VALVE WAS 33.5:1, | | AS OPPOSED TO THE GEAR RATIO OF 75:1 THAT WAS ASSUMED IN THE TEST SETUP | | CALCULATION. | | | | SUBSEQUENT INVESTIGATION ALSO REVEALED THAT THE STROKE TIME OF 7.5 SECONDS | | WAS CONSISTENT WITH TESTING PERFORMED IN 1992. IN 1992, THE STROKE LENGTH | | WAS TYPICALLY ASSUMED TO BE THE SAME AS THE VALVE SIZE. THUS, WITH A 3/4" | | VALVE, THE STROKE LENGTH WAS ASSUMED TO BE 3/4". WITH A GEAR RATIO OF | | 33.5:1, AND A STROKE LENGTH OF 3/4 INCHES, A STROKE TIME OF 7.5 SECONDS WAS | | EXPECTED. APPROXIMATELY ONE YEAR AGO, DATA REVEALED THAT THE ACTUAL STROKE | | LENGTH OF THIS VALVE WAS 1.5 INCHES. WITH THIS CORRECTED STROKE LENGTH, | | THE EXPECTED STROKE TIME WAS NOW CALCULATED TO BE 19.9 SECONDS. WHEN THE | | ACTUAL STROKE TIME WAS FOUND TO BE 7.5 SECONDS, A CONCERN WAS RAISED. | | | | IMMEDIATE CORRECTIVE ACTION WAS TO INVESTIGATE THE STROKE TIME DISCREPANCY | | AND SUBSEQUENTLY CHANGE THE GEAR RATIO OF 1RC-6 TO 75:1. SUBSEQUENT | | DIAGNOSTIC TESTING ASSURED THAT THE NEW STROKE TIME WAS CORRECT AND NO | | OTHER SIGNIFICANT CHANGES OCCURRED DURING THE GEAR CHANGE. | | | | ON DECEMBER 19, 1995, AT 1530, IT WAS DETERMINED THAT THIS VALVE WAS | | CONSIDERED TO BE PAST INOPERABLE, SINCE PRIOR TO 11/24/92, AS IT WOULD NOT | | HAVE BEEN ABLE TO CLOSE AGAINST THE REQUIRED DELTA P DURING THE TIME | | PERIODS IN WHICH A PRESSURIZER SAMPLE WAS BEING TAKEN. THE INABILITY OF | | THIS VALVE TO CLOSE AGAINST THE REQUIRED DELTA P WAS DUE TO THE IMPROPER | | GEAR RATIO. 1RC-6 IS AN ENGINEERED SAFEGUARDS REACTOR BUILDING ISOLATION | | VALVE AND IS REQUIRED TO CLOSE AGAINST A DELTA P OF 1600 PSIG. THIS VALVE | | IS NORMALLY CLOSED, BUT IS REQUIRED TO BE OPENED FOR SAMPLING OF THE | | PRESSURIZER." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29741 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:57 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 16:20[EST]| |NRC NOTIFIED BY: R. VINCENT |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CANIANO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REVISED WEAK-LINK ANALYSIS DETERMINED THAT SELECTED MOTOR-OPERATED VALVES | | COULD BE PHYSICALLY DAMAGED BY A 10 CFR PART 50 APPENDIX R FIRE SCENARIO. | | | | THE FIRE SCENARIO OF CONCERN WOULD CAUSE SPURIOUS MOV OPERATION CONCURRENT | | WITH A LOSS OF VALVE PROTECTIVE CIRCUITRY (THRUST AND LIMIT SWITCHES). | | DAMAGE COULD CAUSE THE VALVE PRESSURE BOUNDARY TO FAIL. SOME OF THE VALVES | | OF CONCERN ARE REQUIRED TO MAINTAIN POST-FIRE SAFE SHUTDOWN SYSTEM | | INTEGRITY. ALL VALVES THAT COULD BE AFFECTED BY THIS POSTULATED FIRE | | SCENARIO REMAIN OPERABLE TO SUPPORT TECHNICAL SPECIFICATION AND APPENDIX R | | REQUIREMENTS IN VIEW OF THE FACT THAT COMPENSATORY FIRE TOURS HAVE BEEN | | IMPLEMENTED FOR THE AREAS OF CONCERN. THIS CONDITION WAS DISCOVERED AS A | | RESULT OF THE LICENSEE'S REEVALUATION OF NRC INFORMATION NOTICE 92-18, | | BASED ON NEW MOV VENDOR INFORMATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29742 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 19:37 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 17:50[CST]| |NRC NOTIFIED BY: KOLB |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CANIANO RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO SEISMIC | | CONCERN REGARDING SOLENOID VALVE. | | | | THE LICENSEE HAS ADMINISTRATIVELY DECLARED THE HPCI SYSTEM INOPERABLE | | BECAUSE SOLENOID VALVE AO1-2301-28 (HPCI DRAIN TRAP BYPASS VALVE) MAY NOT | | FUNCTION DURING A SEISMIC EVENT. FAILURE OF THE VALVE TO OPERATE COULD | | PERMIT WATER TO BACK UP INTO THE HPCI TURBINE. THE LICENSEE PLANS TO | | REORIENT THE SOLENOID FROM HORIZONTAL TO VERTICAL IN ORDER TO RESOLVE THE | | PROBLEM. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29743 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 20:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 19:57[EST]| |NRC NOTIFIED BY: GWIRTZ |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAJOR LOSS OF OFFSITE RESPONSE CAPABILITY DUE TO WINTER STORM. | | | | DUE TO AN ONGOING WINTER STORM, GREATER THAN 10% OF THE LICENSEE'S OFFSITE | | EMERGENCY WARNING SIRENS ARE INOPERABLE. THE LICENSEE REPORTED THAT TEN | | SIRENS IN DELAWARE AND ONE SIREN IN NEW JERSEY ARE PRESENTLY INOPERABLE | | BECAUSE OF POWER FAILURES. THE STATE OF DELAWARE IS NOTIFYING ROUTE | | ALERTING TEAMS AS A BACKUP DUE TO THE LOSS OF THE SIRENS. THIS CONDITION | | AFFECTS BOTH SALEM 1 AND 2, AS WELL AS HOPE CREEK. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | THIS EVENT WAS ALSO REPORTED BY HOPE CREEK. SEE EVENT 29745. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29744 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 20:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 20:00[EST]| |NRC NOTIFIED BY: GWIRTZ |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL VITAL 4KV BUSES DECLARED INOPERABLE DUE TO DEGRADED SWITCHES IN | | SWITCHGEAR BREAKERS. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FOLLOWUP INVESTIGATION TO A FAILURE IN A 4KV BREAKER AUXILIARY CONTACT | | SWITCH HAS INDICATED A FAILURE MECHANISM WHICH APPLIES TO ALL VITAL 4KV | | SWITCHGEAR ON UNITS 1 AND 2. A LEXAN PLASTIC MATERIAL IN THESE SWITCHES IS | | SHOWING INDICATIONS OF EITHER STRESS OR HYDROCARBON CORROSION FAILURES | | WHICH COULD RESULT IN THE AUXILIARY CONTACTS FAILING TO MAKE UP. THESE | | SWITCHES ARE USED FOR BREAKER POSITION SWITCHES AND BREAKER CONTACT | | AUXILIARY SWITCHES. AS A RESULT, ALL 4KV VITAL BUSES AND SUBSEQUENT | | EQUIPMENT HAS BEEN DECLARED INOPERABLE. APPLICABLE TECHNICAL | | SPECIFICATIONS CONSIST OF REQUIREMENT FOR RADIATION MONITORING EQUIPMENT | | AND FUEL HANDLING BUILDING VENTILATION. MANUAL BREAKER OPERATION WOULD | | STILL BE AVAILABLE IF REQUIRED TO MAINTAIN SPENT FUEL PIT COOLING. THE | | MANUFACTURER REPORTED A FAILURE RATE OF THESE SWITCHES AS LOW AS | | APPROXIMATELY 0.03%. ALL SALEM SYSTEMS WILL BE WALKED DOWN TO LOCATE USES | | OF THESE SWITCHES." | | | | THE LICENSEE STATED THAT THE SWITCHES ARE FROM AN UNKNOWN VENDOR, BUT THAT | | THEY ARE INSTALLED IN GENERAL ELECTRIC SWITCHGEAR. ADDITIONALLY, MAINE | | YANKEE HAS HAD SIMILAR PROBLEMS WITH THESE SWITCHES AND HAS REPLACED THEM. | | THE LICENSEE IS INVESTIGATING THE POSSIBILITY OF A PART 21 REPORT. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29745 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/19/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 21:16 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/19/95 | +------------------------------------------------+EVENT TIME: 20:25[EST]| |NRC NOTIFIED BY: DeDOMENICO |LAST UPDATE DATE: 12/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAJOR LOSS OF OFFSITE RESPONSE CAPABILITY DUE TO WINTER STORM. | | | | AT 2025, THE CONTROL ROOM WAS NOTIFIED BY THE SALEM CONTROL ROOM THAT TEN | | OF THE LICENSEE'S OFFSITE NOTIFICATION SIRENS IN DELAWARE AND ONE LOCATED | | IN NEW JERSEY ARE INOPERABLE DUE TO AN ONGOING WINTER STORM. (SEE EVENT | | 29743.) THE STATE OF DELAWARE IS NOTIFYING ROUTE ALERTING TEAMS AS A | | BACKUP DUE TO THE LOSS OF THE SIRENS. THE SIRENS WILL BE RETURNED TO | | SERVICE AS SOON AS POWER CAN BE RESTORED. THE NRC RESIDENT INSPECTOR WILL | | BE INFORMED BY THE LICENSEE. | | | | THIS EVENT WAS ALSO REPORTED BY SALEM. SEE EVENT 29743. | +------------------------------------------------------------------------------+